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NSR database version of May 20, 2024.

Search: Author = O.Bouland

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2024BO01      Nucl.Data Sheets 193, 105 (2024)

O.Bouland, P.Marini

First simultaneous evaluation of fission probabilities and neutron-induced cross sections for the Pu fissile isotopes

NUCLEAR REACTIONS 237,238,240,242,244Pu(n, F), E=4-8 MeV; analyzed available data; deduced recommended σ from measured deexcitation probabilities in a consistent and rigorous theoretical framework describing both charged-particle and neutron-induced surrogate reactions, fission probabilities, fission-barrier heights, issues with he normalization of some fission probabilities measured in the 70s in (t, p) reactions.

doi: 10.1016/j.nds.2024.01.005
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2021ME12      Phys.Rev. C 103, 054609 (2021)

V.Meot, O.Roig, B.Laurent, P.Morel, J.Aupiais, O.Delaune, G.Haouat, O.Bouland

239Pu(n, 2n)238Pu cross section measurement using a recoil method

NUCLEAR REACTIONS 239Pu(n, 2n)238Pu, E=7.1, 7.7, 9.3 MeV; 238U(n, 2n)237U, E=7, 8, 15.3, 15.8 MeV; measured Eγ, Iγ, Eα, Iα from decays of residual products at the high-flux fast-neutron facilities of the CEA-DAM Ile de France; deduced σ(E), disagreement with JEFF3.3 evaluation. Comparison with previous experimental results, and with evaluated data in JEFF3.3 and ENDF/B-VIII.0.

doi: 10.1103/PhysRevC.103.054609
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23777.

2020BO18      Phys.Rev. C 102, 054608 (2020)

O.Bouland, G.Noguere

Reconciling surrogate-reaction probabilities and neutron-induced cross sections

NUCLEAR REACTIONS 240Pu(α, α')240Pu*, E*=4.6-8 MeV; calculated fission and γ probabilities as function of excitation energy of the compound system using AVXSF-LNG code with TALYS Jπ distributions, and compared with surrogate-reaction method (SRM) based estimates using JEFF-3.3 cross sections. 240Pu*,241Pu*,242Am*; calculated cumulative number of levels as a function of the excitation energy (<5 MeV) on top of the outer fission barrier using the combinatorial quasiparticle-vibrational-rotational level density method. 174Yb(3He, p)176Lu*, E*=6-7.5 MeV; calculated γ-ray emission probability for direct reaction as a function of excitation energy of the compound system using the AVXSF-LNG CODE with a uniform spin-parity entrance distribution, and compared with SRM-based calculations. 176Lu*; calculated width fluctuation correction factors, involved in the calculation of neutron-induced average cross sections of 175Lu, as a function of excitation energy (6.4-9.2 MeV) of 176Lu. 175Lu(n, γ), E=20-1000 keV; calculated radiative-capture σ(E) using the extended surrogate-reaction method (ESRM) transformation of the experimental γ-ray emission probability data set from 2012Bo08, and compared with evaluated and other experimental data. Discussed application of new ERSM as a technique to jointly analyze γ-ray probability and cross section data.

doi: 10.1103/PhysRevC.102.054608
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2020PE08      Phys.Rev.Lett. 125, 122502 (2020)

R.Perez Sanchez, B.Jurado, V.Meot, O.Roig, M.Dupuis, O.Bouland, D.Denis-Petit, P.Marini, L.Mathieu, I.Tsekhanovich, M.Aiche, L.Audouin, C.Cannes, S.Czajkowski, S.Delpech, A.Gorgen, M.Guttormsen, A.Henriques, G.Kessedjian, K.Nishio, D.Ramos, S.Siem, F.Zeiser

Simultaneous Determination of Neutron-Induced Fission and Radiative Capture Cross Sections from Decay Probabilities Obtained with a Surrogate Reaction

NUCLEAR REACTIONS 240Pu(α, α'), (α, F), E=30 MeV; 239Pu(n, F), (n, γ), E<2 MeV; measured reaction products, Eγ, Iγ, Eα, Iα, α-fission fragment-γ ray triple coin.; deduced 239Pu σ as a function of energy. Comparison with ENDF/B-VIII.0, JENDL 4.0. JEFF 3.3 libraries.

doi: 10.1103/PhysRevLett.125.122502
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23769.

2019BO18      Phys.Rev. C 100, 064611 (2019)


Reexamining fission-probability data using R-matrix Monte Carlo simulations: Beyond the surrogate-reaction method

NUCLEAR REACTIONS 235U(n, F), E=0.001, 0.1, 1, 5 MeV; 238Pu(t, pF), 239Pu(d, pF), E=5 MeV; 238Pu(n, F), E=0.001, 1 MeV; 239,240Pu(n, n), (n, n'), (n, γ), (n, F), E=0.001-2 MeV; 241Pu(n, F), E*=5.2-7 MeV; calculated total angular momentum population distribution, partial σ(E), neutron-fed transfer partial decay probabilities, sub-barrier tunneling estimates, double-barrier fission surrogate reaction probabilities, γ-decay probability, neutron emissions from positive- and negative-parity states, fission decay probabilities as a function of excitation energy and resonance spins using one-dimensional fission barrier extended R-matrix Monte Carlo simulations of neutron-induced cross sections together with surrogate-reaction decay probabilities.

doi: 10.1103/PhysRevC.100.064611
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2019NO09      Phys.Rev. C 100, 065806 (2019)

G.Noguere, O.Bouland, J.Heyse, S.Kopecky, C.Paradela, P.Schillebeeckx, A.Ebran, O.Roig

s-wave average neutron resonance parameters of 175Lu + n

NUCLEAR REACTIONS 175Lu(n, γ), E=0.001-1 keV; measured neutron spectra using time-of-flight technique at the GELINA facility of JRC-Geel; deduced resonances, resonance parameters, energies, J, π, Γn, Γγ of 214 n-resonances up to 1 keV, average radiation width. Resonance parameters used the neutron resonance shape analysis technique and the Reich-Moore approximation of the R-matrix theory. Reviewed previous experimental and evaluated Lu(n, γ) data. 175Lu(n, γ), E=100 eV to 10 MeV; calculated shape-elastic and total σ(E) using the ECIS code, capture σ times the square root of the incident neutron energy using the TALYS code, and compared with available experimental data.

doi: 10.1103/PhysRevC.100.065806
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23728.

2018CH12      Nucl.Data Sheets 148, 189 (2018)

M.B.Chadwick, R.Capote, A.Trkov, M.W.Herman, D.A.Brown, G.M.Hale, A.C.Kahler, P.Talou, A.J.Plompen, P.Schillebeeckx, M.T.Pigni, L.Leal, Y.Danon, A.D.Carlson, P.Romain, B.Morillon, E.Bauge, F.-J.Hambsch, S.Kopecky, G.Giorginis, T.Kawano, J.Lestone, D.Neudecker, M.Rising, M.Paris, G.P.A.Nobre, R.Arcilla, O.Cabellos, I.Hill, E.Dupont, A.J.Koning, D.Cano-Ott, E.Mendoza, J.Balibrea, C.Paradela, I.Duran, J.Qian, Z.Ge, T.Liu, L.Hanlin, X.Ruan, W.Haicheng, M.Sin, G.Noguere, D.Bernard, R.Jacqmin, O.Bouland, C.De Saint Jean, V.G.Pronyaev, A.V.Ignatyuk, K.Yokoyama, M.Ishikawa, T.Fukahori, N.Iwamoto, O.Iwamoto, S.Kunieda, C.R.Lubitz, M.Salvatores, G.Palmiotti, I.Kodeli, B.Kiedrowski, D.Roubtsov, I.Thompson, S.Quaglioni, H.I.Kim, Y.O.Lee, U.Fischer, S.Simakov, M.Dunn, K.Guber, J.I.Marquez Damian, F.Cantargi, I.Sirakov, N.Otuka, A.Daskalakis, B.J.McDermott, S.C.van der Marck

CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen

NUCLEAR REACTIONS 1H, 16O, 56Fe, 235,238U, 239Pu(n, X), E<20 MeV; analyzed available data; calculated σ, σ(θ), σ(θ, E).

doi: 10.1016/j.nds.2018.02.003
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2018LY03      Phys.Rev. C 97, 064601 (2018)

J.E.Lynn, P.Talou, O.Bouland

Reexamining the role of the (n, γf) process in the low-energy fission of 235U and 239Pu

NUCLEAR REACTIONS 239Pu(n, γF), E=10-110 eV; 239Pu(n, γF), E=0-40 eV; compiled experimental and evaluated (from ENDF/B-VII.1) data for average prompt fission neutron multiplicity; calculated M1 and E1 photon strength functions, reaction widths, prefission γ-ray spectrum and spin- and parity-dependent fission probabilities for 240Pu* using secondary and tertiary vibrational model, resonance parameters. 235U, 239Pu(n, γF), E=0.001-2 MeV; calculated capture and fission σ(E), compound nucleus level density, M1 scissors mode contributions to the total γ strength function. 239Pu(n, F), E=0-210 MeV; 235U(n, F), E=0-100 MeV; calculated average total kinetic energy (TKE) of the fission fragments, and compared with experimental values. 235U(d, pF), 238Pu(t, pF), E*=4.5-6.5 MeV; calculated fission probability. Comparison with experimental values.

doi: 10.1103/PhysRevC.97.064601
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2015NO03      Phys.Rev. C 92, 014607 (2015)

G.Noguere, O.Bouland, S.Kopecky, C.Lampoudis, P.Schillebeeckx, A.Plompen, F.Gunsing, C.Sage, I.Sirakov

Partial-wave analysis of n + 241Am reaction cross sections in the resonance region

NUCLEAR REACTIONS 241Am(n, γ), E<150 eV; analyzed and evaluated time-of-flight cross section data from experiments carried out at the GELINA, LANSCE, ORELA and Saclay facilities with optical model calculations; deduced resonances, σ(E), widths and resonance parameters from resonance shape analysis of transmissions, capture yields, fission yields, neutron strength function, mean level spacing, average radiation width for s-wave resonances, neutron strength functions for higher partial waves together with channel and effective scattering radii. R-matrix analysis using the RFIT code. Comparison with calculations using the ECIS, TALYS and CONRAD computer codes.

doi: 10.1103/PhysRevC.92.014607
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Data from this article have been entered in the XUNDL database. For more information, click here.

2015TA26      Eur.Phys.J. A 51, 181 (2015)

P.Tamagno, C.De Saint Jean, O.Bouland, G.Noguere, P.Archier, E.Privas, O.Serot

From low- to high-energy nuclear data evaluations - Issues and perspectives on nuclear reaction models and covariances

doi: 10.1140/epja/i2015-15181-1
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2014BO14      Nucl.Data Sheets 118, 211 (2014)

O.Bouland, J.E.Lynn, P.Talou

The Impact of Intermediate Structure on the Average Fission Cross Sections

NUCLEAR REACTIONS 239,240Pu(n, F), E not given; calculated width fluctuation correction factor, average fission σ using Porter-Thomas hypothesis within Monte Carlo R-matrix.

doi: 10.1016/j.nds.2014.04.039
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2014CH24      Nucl.Data Sheets 118, 1 (2014)

M.B.Chadwick, E.Dupont, E.Bauge, A.Blokhin, O.Bouland, D.A.Brown, R.Capote, A.Carlson, Y.Danon, C.De Saint Jean, M.Dunn, U.Fischer, R.A.Forrest, S.C.Frankle, T.Fukahori, Z.Ge, S.M.Grimes, G.M.Hale, M.Herman, A.Ignatyuk, M.Ishikawa, N.Iwamoto, O.Iwamoto, M.Jandel, R.Jacqmin, T.Kawano, S.Kunieda, A.Kahler, B.Kiedrowski, I.Kodeli, A.J.Koning, L.Leal, Y.O.Lee, J.P.Lestone, C.Lubitz, M.MacInnes, D.McNabb, R.McKnight, M.Moxon, S.Mughabghab, G.Noguere, G.Palmiotti, A.Plompen, B.Pritychenko, V.Pronyaev, D.Rochman, P.Romain, D.Roubtsov, P.Schillebeeckx, M.Salvatores, S.Simakov, E.Sh.Soukhovitskii, J.C.Sublet, P.Talou, I.Thompson, A.Trkov, R.Vogt, S.van der Marck

The CIELO Collaboration: Neutron Reactions on 1H, 16O, 56Fe, 235, 238U, and 239Pu

COMPILATION 1H, 16O, 56Fe, 235,238U, 239Pu(n, x), E≈0-20 MeV; analyzed available data on σ, neutron multiplicity, criticality using ENDF/B-VII.1, JENDL-4.0, JEFF-3.1, ROSFOND 2010, CENDL-3.1, EAF-2010 evaluated nuclear libraries, Atlas of Neutron Resonances, Neutron Cross Section Standards evaluations; deduced recommendations for CIELO library, parameters, Maxwellian-averaged, thermal, californium σ, Westcott factors, resonance integrals. Compared with available data.

doi: 10.1016/j.nds.2014.04.002
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2013BO29      Phys.Rev. C 88, 054612 (2013); Erratum Phys.Rev. C 101, 039901 (2020)

O.Bouland, J.E.Lynn, P.Talou

R-matrix analysis and prediction of low-energy neutron-induced fission cross sections for a range of Pu isotopes

NUCLEAR REACTIONS 236,237,238,239,240,241,242,243,244Pu(n, F), 236,240,241,243Pu(n, γ), 236,243Pu(n, n'), E=0.005-5 MeV; calculated σ(E). 237,238,239,240,241,242,243,244,245Pu; calculated inner and outer fission barrier heights, neutron and proton pairing gaps. Hauser-Feshbach statistical theory, and fission decay channel in the R-matrix formalism. Comparison with several previous theoretical and empirical calculations and evaluated data libraries. 243Pu predicted to be fissile in contrast to data in ENDF/B-VII.1 and JEFF-3.1.2 evaluated libraries. Discussed level spacing distributions.

doi: 10.1103/PhysRevC.88.054612
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2013LA34      Eur.Phys.J.Plus 127, 86 (2013)

C.Lampoudis, S.Kopecky, O.Bouland, F.Gunsing, G.Noguere, A.J.M.Plompen, C.Sage, P.Schillebeeckx, R.Wynants

Neutron transmission and capture cross section measurements for 241Am at the GELINA facility

NUCLEAR REACTIONS 241Am(n, γ), (n, X), E<110 eV; measured reaction products, Eγ, Iγ; deduced σ, yield, resonance parameters. Comparison with available data, JEFF and JENDL evaluated nuclear libraries.

doi: 10.1140/epjp/i2013-13086-0
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2012BE16      J.Nucl.Sci.Technol.(Tokyo) 49, 132 (2012)

D.Bernard, O.Bouland

Americium-241 phase I: reevaluation for JEFF-3.1.1 and a step forward

NUCLEAR REACTIONS 241Am(n, X), (n, F), (n, γ), E<20 MeV; calculated σ, isomeric ratios distributions. Comparison with EXFOR, Atlas of Neutron Resonances and JEF-2.2, JENDL-3.3, ENDF/B-VII.0, BROND-3 evaluated nuclear libraries.

doi: 10.1080/18811248.2011.636567
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2011BO25      J.Korean Phys.Soc. 59, 833s (2011)

O.Bouland, G.M.Hale, J.E.Lynn, P.Talou, D.Bernard, O.Litaize, G.Noguere, C.De saint Jean, O.Serot

Towards Consistent Nuclear Models and Comprehensive Nuclear Data Evaluations

NUCLEAR REACTIONS 12C(n, X), E=0-6.5 MeV; analyzed σ using R matrix; deduced resonance widths. A=60-175(n, n'), E not given; calculated average prompt neutron multiplicity.

doi: 10.3938/jkps.59.833
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2011LA19      J.Korean Phys.Soc. 59, 1785s (2011)

C.Lampoudis, S.Kopecky, A.Plompen, P.Schillebeeckx, P.Siegler, F.Gunsing, C.Sage, O.Bouland

Transmission and Capture Measurements for 241Am at GELINA

NUCLEAR REACTIONS 241Am(n, n'), (n, γ), E=0.1-100 eV; measured En, In, Eγ, Iγ; deduced capture yields, transmission; calculated capture yields, transmission using R-matrix.

doi: 10.3938/jkps.59.1785
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2011TA21      J.Korean Phys.Soc. 59, 797s (2011)

P.Talou, T.Kawano, J.E.Lynn, P.Moller, O.Bouland, M.B.Chadwick

Recent Advances in Nuclear Fission Theory: Pre- and Post-Scission Physics

NUCLEAR REACTIONS 239,240,241,242Pu(n, f), E≈0.01-20 MeV; calculated σ using R-matrix formalism in Bjornholm-Lynn model. 235U(n, f), E=thermal, 0.5 MeV; calculated prompt fission neutron multiplicity using Monte Carlo Hauser-Feshbach; compared to data, ENDF/B-VII.0.

doi: 10.3938/jkps.59.797
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2010SA15      Phys.Rev. C 81, 064604 (2010)

C.Sage, V.Semkova, O.Bouland, P.Dessagne, A.Fernandez, F.Gunsing, C.Nastren, G.Noguere, H.Ottmar, A.J.M.Plompen, P.Romain, G.Rudolf, J.Somers, F.Wastin

High resolution measurements of the 241Am(n, 2n) reaction cross section

NUCLEAR REACTIONS 241Am(n, 2n), E=8-21 MeV; measured Eγ, Iγ; deduced σ, σ(E) by activation method. Comparison with nuclear model calculations using the TALYS code, and with evaluated data such as ENSDF/B-VII.

doi: 10.1103/PhysRevC.81.064604
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23114.

2006NO12      Phys.Rev. C 74, 054602 (2006)

G.Noguere, O.Bouland, A.Brusegan, P.Schillebeeckx, P.Siegler, A.Lepretre, N.Herault, G.Rudolf

Neutron capture and total cross sections of 127I and 129I

NUCLEAR REACTIONS 127,129I(n, γ), (n, X), E=0.0005-100 keV; measured transmission and capture σ; deduced resonance parameters.

doi: 10.1103/PhysRevC.74.054602
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset22948. Data from this article have been entered in the XUNDL database. For more information, click here.

2005BA78      Nucl.Sci.Eng. 151, 135 (2005)

R.Babut, O.Bouland, E.Fort

Reich-Moore Parameterization of (α, n) Reactions on Light Nuclei: Impact on a Neutron Source Calculation in an Oxide Fuel

NUCLEAR REACTIONS 17,18O(α, n), E ≈ 1100-5500 keV; 20Ne(n, α), E ≈ 2500-5000 keV; analyzed σ; deduced parameters.

doi: 10.13182/NSE05-A2536
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2001FR10      Nucl.Sci.Eng. 137, 70 (2001)

F.H.Frohner, O.Bouland

Treatment of External Levels in Neutron Resonance Fitting: Application to the nonfissile nuclide 52Cr

NUCLEAR REACTIONS 52Cr(n, γ), (n, X), E < 1400 keV; calculated capture, transmission σ, inclusion of external levels in resonance fitting. Comparisons with data.

2000FR16      Trans.Bulg.Nucl.Soc. 5, 54 (2000)

F.H.Frohner, O.Bouland

Handling of External Levels in Neutron Resonance Fitting

NUCLEAR REACTIONS 52Cr(n, X), E ≈ 50-450 keV; calculated transmission spectrum. Comparison with data.

1997BO46      Nucl.Sci.Eng. 127, 105 (1997)

O.Bouland, H.Derrien, N.M.Larson, L.C.Leal

R-Matrix Analysis of the 240Pu Neutron Cross Sections in the Thermal to 5700-eV Energy Range

NUCLEAR REACTIONS 240Pu(n, X), E=0.02-5700 eV; analyzed transmission, fission, total σ; deduced parameters. R-matrix analysis.

doi: 10.13182/NSE127-105
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